|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start Instrumentation,Cp & Exhaust Isolation Instrumentation & LTOP PORV TS Trip Setpoints as Nominal Values ML20204E5281999-03-15015 March 1999 Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20204F6931999-03-11011 March 1999 Proposed Tech Specs 3.3.7 & 3.3.8 Re CR Area Ventilation Sys & Auxiliary Bldg Filtered Ventilation,Exhaust Sys Actuation Instrumentation ML20203A3331999-01-28028 January 1999 Proposed Tech Specs Modifying Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20197G8991998-12-0707 December 1998 Proposed ITS 3.8.3,modifying Inventory Requirements for DG Lube Oil Sys ML20195D6481998-11-11011 November 1998 Proposed Tech Specs,Modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys at Plant ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20151Y1821998-09-15015 September 1998 Proposed Improved TSs Providing Changes Necessary to Resolve Items Identified by Util During Review ML20151T9491998-09-0808 September 1998 Proposed Tech Specs & Bases Re Relocation from Current TS & Scheduling of New More Restrictive Surveillance Requirements ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5751998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.2 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A6571998-08-0606 August 1998 TS Page 3/4 8-9 Re Notice of Enforcement Discretion Request from Enforcing TS Surveillance Requirement 4.8.1.1.2i.2 ML20237A9341998-08-0606 August 1998 Proposed Tech Specs,Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20237A0361998-08-0505 August 1998 Suppl 8 to Improved TS (Its),Combining Units ITS Pages to Facilitate Ease of Use & Significantly Reduce Vol of Paper That Must Be Processed & Controlled ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20249B3961998-06-15015 June 1998 Proposed Tech Specs Affecting Requirements for low-temp Overpressure Protection ML20248B5741998-05-22022 May 1998 Proposed Tech Specs Modifying SR 4.4.3.3 for Pressurizer Heaters to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved Tech Specs ML20217E9831998-04-20020 April 1998 Proposed Improved Tech Specs Sections 1.0,2.0,3.0 & 4.0 ML20217E9521998-04-20020 April 1998 Proposed Tech Specs Revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation Function,Which Is Part of ESFAS ML20216B9721998-04-0808 April 1998 Proposed Tech Specs 3/4.6.5 Re Ice Condenser Reduction of Required Ice Weight ML20217C7121998-03-20020 March 1998 Proposed Improved TS Section 3.6 Re Containment Sys ML20216B7691998-03-0909 March 1998 Proposed Tech Specs Pages Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Also Included ML20217Q3741998-03-0303 March 1998 Proposed Tech Specs Re Catawba Safety Review Group ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20203H9241997-12-11011 December 1997 Proposed Tech Specs Re ESFAS Instrumentation ML20210U6401997-09-15015 September 1997 Proposed Tech Specs Revising Pressure/Temp Limits, Overpressure Protection & Reactor Vessel Matl ML20140A6201997-05-27027 May 1997 Proposed Tech Specs Deleting References to Steam Generator Tube Sleeving & Repair That Will Not Be Used for Westinghouse Model D5 Steam Generators in Use at Catawba Unit 2 ML20140A6681997-05-27027 May 1997 Proposed Tech Specs,Removing Surveillance Requirement 4.7.13.3a.2 Which Specifies 112,320 Gallon Min Volume of Borated Water Be Available to Supply Standby Makeup Pump ML20141C2281997-05-0808 May 1997 Proposed Tech Specs Allowing Natural Circulation Testing in Mode 3 Following Steam Generator Replacement for Catawba Unit 1 ML20136G2471997-03-0707 March 1997 Proposed Tech Specs Re SGTR Evaluation ML20133E6801997-01-0303 January 1997 Proposed Tech Specs to Eliminate SI Signal on Low Steam Line Pressure.Unnecessary SI Actuation Causes Unnecessary Challenges to Plant Safety Sys,Unnecessary Thermal Transient & Increases Actuation Cycles ML20132F0631996-12-12012 December 1996 Proposed Tech Specs,Section 3/4.3.3.1,for Units 1 & 2 Clarifying Info Re Operation of Radiation Monitors for Plant Operations ML20134H3281996-11-0404 November 1996 Proposed Tech Specs to Licenses NPF-35 & NPF-52,eliminating During Shutdown Restriction for 18 Month Standby Shutdown Sys DG Insp TS Surveillance 4.7.13.1.c ML20113G4431996-09-21021 September 1996 Proposed Tech Specs 8.3 Re Onsite Power Systems ML20117K1011996-08-29029 August 1996 Proposed Tech Specs,Replacing 960516 Response to Concerns Re Proposed Changes for Diesel Starting Air Sys Surveillance Testing ML20116K4601996-08-0808 August 1996 Proposed Tech Specs 6.9.1.9 Re Listings of Core Operating Limit Methodologies ML20113C7201996-06-21021 June 1996 Proposed Tech Specs 3.9.6,revising Term Lifting Loads to Lifting Force Used in Manipulator Crane TS 3.9.6b.2 & Redefining Auxiliary Hoist Min Capacities ML20112G9961996-06-0606 June 1996 Proposed Tech Specs,Reflecting Separate Volumes ML20112F6311996-06-0505 June 1996 Proposed Tech Specs 3/4.6 Re Containment Systems & 3/4.6.1 Re Primary Containment Integrity ML20112A7571996-05-16016 May 1996 Proposed Tech Specs 3/4.8 Re Surveillance Requirements ML20101M4741996-04-0303 April 1996 Proposed TS 3/4.6.4.3 & Bases Re Hydrogen Mitigation Sys ML20101H6101996-03-15015 March 1996 Proposed Tech Specs Re Replacement of SGs ML20100P0521996-03-0404 March 1996 Proposed Tech Specs Re Rev to 10CFR50,App J Which Provided for Reduced Test Frequency for Qualified Containment ML20096E8611996-01-19019 January 1996 Proposed Tech Specs,Providing Approved Revs to TS 6.9.1.9 to Incorporate Anticipated Revs to TRs DPC-NE-3000P-A & DPC-3002-A ML20096E5951996-01-12012 January 1996 Proposed Tech Specs Re Containment Leak Rate Testing Requirements of 10CFR50 App J,Option B 1999-09-16
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications ML20210N9641999-07-26026 July 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20211C3731999-07-26026 July 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual & List of Effective Pages ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20210A5911999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20216D4061999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitment Manual, List of Effective Pages ML20211C3751999-05-19019 May 1999 5 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program. Page 1 of 15 in Section 4.1 of Incoming Submittal Not Included ML20195B4181999-05-18018 May 1999 Revised Pages to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206T0571999-05-0505 May 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual. with List of Effective Pages ML20206J4531999-04-22022 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206Q8741999-04-22022 April 1999 Revs to CNS Selected Licensee Commitments Manual,Including Page 5 of List of Effective Pages & Pages 1-11 to Chapter 16.9-13.With ML20206B1271999-04-15015 April 1999 CNS Selected Licensee Commitments Manual, List of Effective Pages ML20206C0391999-04-15015 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start Instrumentation,Cp & Exhaust Isolation Instrumentation & LTOP PORV TS Trip Setpoints as Nominal Values ML20204G2541999-03-16016 March 1999 Revised Pages to Catawba Nuclear Station Licensee Commitments Manual ML20204E5281999-03-15015 March 1999 Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20204F6931999-03-11011 March 1999 Proposed Tech Specs 3.3.7 & 3.3.8 Re CR Area Ventilation Sys & Auxiliary Bldg Filtered Ventilation,Exhaust Sys Actuation Instrumentation ML20205B1341999-03-11011 March 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20204E7271999-03-0808 March 1999 Chapter 16.5-2,page 1-3 to CNS Selected Licensee Commitments Manual. with List of Effective Pages ML20203A3331999-01-28028 January 1999 Proposed Tech Specs Modifying Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20199H4061999-01-16016 January 1999 Revised CNS Selected Licensee Commitments Manual ML20197G8991998-12-0707 December 1998 Proposed ITS 3.8.3,modifying Inventory Requirements for DG Lube Oil Sys ML20195D6481998-11-11011 November 1998 Proposed Tech Specs,Modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys at Plant ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20151Y1821998-09-15015 September 1998 Proposed Improved TSs Providing Changes Necessary to Resolve Items Identified by Util During Review ML20151T9491998-09-0808 September 1998 Proposed Tech Specs & Bases Re Relocation from Current TS & Scheduling of New More Restrictive Surveillance Requirements ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5751998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.2 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A6571998-08-0606 August 1998 TS Page 3/4 8-9 Re Notice of Enforcement Discretion Request from Enforcing TS Surveillance Requirement 4.8.1.1.2i.2 ML20237A9341998-08-0606 August 1998 Proposed Tech Specs,Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20237A0361998-08-0505 August 1998 Suppl 8 to Improved TS (Its),Combining Units ITS Pages to Facilitate Ease of Use & Significantly Reduce Vol of Paper That Must Be Processed & Controlled ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236P8671998-07-0606 July 1998 Updated Pages to Catawba Nuclear Station Selected License Commitments Manual ML20249B3961998-06-15015 June 1998 Proposed Tech Specs Affecting Requirements for low-temp Overpressure Protection ML20249B6221998-06-11011 June 1998 Revised Table of Contents for Chapter 16 of Selected License Commitments Manual ML20248B5741998-05-22022 May 1998 Proposed Tech Specs Modifying SR 4.4.3.3 for Pressurizer Heaters to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved Tech Specs ML20247Q9871998-05-11011 May 1998 Revised Chapter 16 to Selected License Commitment Manual ML20217E9521998-04-20020 April 1998 Proposed Tech Specs Revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation Function,Which Is Part of ESFAS ML20217E9831998-04-20020 April 1998 Proposed Improved Tech Specs Sections 1.0,2.0,3.0 & 4.0 ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20216B9721998-04-0808 April 1998 Proposed Tech Specs 3/4.6.5 Re Ice Condenser Reduction of Required Ice Weight ML20217C7121998-03-20020 March 1998 Proposed Improved TS Section 3.6 Re Containment Sys ML20216B7691998-03-0909 March 1998 Proposed Tech Specs Pages Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Also Included ML20217Q3741998-03-0303 March 1998 Proposed Tech Specs Re Catawba Safety Review Group ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR 1999-09-16
[Table view] |
Text
- - - - _ -_ - . -. . . - - -. ._ . _ - . _ ,
d
. .' MC dMTdfdT 8.3 Onsite Power Systems Catawba Nuclear Station l
I 1
I 8.3.2.2.4 Compliance with Regulatory Guide 1.32, IEEE Standard 308-19 74, and IEEE Standard I
450-1975 and IEEE 450 1980 -
j _--- -
3081974 as augmented j e design Class . de power syst s co . es with the requirements e 1.32. The Class tteries are given a service te interval not to exceed 18 by Regulatory v, the Class IE ba rformance and accep e tests ply with Section 5 of months. Ad
, IEEE 450-1 andi etion 6 of IE 450-1 8.3.2.2.5 Class 1E Equipment Qualification Requirements The seismic and environmental qualifications of Class IE de power system equipment are discussed in Sections 3.10, " Seismic Qualification of Seismic Category 1 Instrumentation and Electrical Equipment" on on page 3-219 and 3.11, "Emironmental Design of Mechanical and Electrical Equipment" page 3-223, respectively.
8.3.2.3 Physical identification of Class 1E Equipment l
The physical identification of the Class IE de systems equipment is discussed in Section 8.3.1.3, " Physical Identification of Class IE Equipment" on page 8 38.
8.3.2.4 Independence of Redundant Systems The independence of redundant Class lE de systems is discussed in Section 8.3.1.4, " Independence of Redundant Systems" on page 8 38.
THIS IS THE LAST PAGE OF THE CHAPTER S TEXT PORTION.
Replace UFSAR section 8.3.2.2.4 with the following: _
"The design of Class 1E DC power systems complies with the requirements of IEEE 308-1974 as augmented by Regulatory Guide 1.32 with the following clarification:
In general, protective devices on the 125 VDC Vital Instrumentation and Control Power System (EPL) are selected and set so that a minimal amount of equipment is isolated from the system for adverse conditions such as a fault.
Protective devices protect cable and equipment. In the case of DC distribution system breakers that may not fully coordinate, the resulting ar.ount of equipment isolation is acceptable, such that there is no impact on the UFSAR Chapter 15 safety analyses and redundant egyipment is not .
affected. l The Class 1E batteries are given a service test at an interval not to exceed 18 months. Additionally, the Class 1E battery performance and acceptance tests comply with Section 5 of IEEE 450-1975 and/or section 6 of IEEE 450-1980." -
g (30 NOV 1995) 9609270217 960921 PDR ADOCK 05000413 P PDR
~
8.3 Onsite Power Systems k The631 l Catawba Nuclear Station
- 1) 50/51 (Instantaneous / Time 50-1.73 X Iocked Rotor Current Delayed OC) 51 125 to 200% Full Load Current
' f (Coordinated with Motor Starting and Thermal Damage Curve) hh di Oni Y'
- 2) 50G (Ground Overcurrent) 5 Amps at 6 Cycles i 111. Transformer Protection 4)0 g 4"Ko l ANSI Number and Function Setting pqc '5
- 1) 50/51 (Inst./ Time Delayed OC) 50-1.73 X Maximum low Side Fault Curren ()R.-
51-125 to 150% Transformer Full load Current
- 2) 50G (Ground Overcurrent) 5 Amps at 6 Cycles To avoid protective relay trip setpoint drift problems, all Class IE relays are tested periodically to verify the relays are within specified limits and are re-calibrated if required.
8.3.1.1.2.2 600VAC Essential Auxiliary Power System 2 Note:
2 This section of the FSAR contains information on the design bases and design criteria of this 2 system / structure. Additional information that may assist the reader in understanding the system is 2 contained in the design basis document (DBD) for this system / structure.
The 600VAC Essential Auxiliary Power System supplies power to the 600 volt essential motor control centers which are located in load concentration areas throughout the plant. Connected to the essential motor control centers are all of the 600 volt essential loads which require power during accident l conditions and non-essentialloads which are required to be disconnected during accident conditions. Two essential motor control centers (IEMXG and 2EMXH) are provided to supply power to loads which are ;
shared between the two units, e.g. Control Area Chilled Water System. The Train A loads, fed from motor control center IEMXG, are identified in Table 8-6 in the remarks column. The corresponding Train B loads are fed from 2EMXH. This system is shown on Figure 8-21.
The only non-Class IE loads which can be powered from the Class IE AC systems during an accident are the AC emergency lighting transformers and the hydrogen igniter transformers. These loads are automatically disconnected on a LOCA signal and are given a permissive signal which allows manual connection after all LOCA loads are sequenced on. The AC emergency lighting transformers are powered from 600 volt Class IE motor control centers IEMXA, IEMXJ,2EMXA and 2EMXJ. The hydrogen igniter transformers are fed from 600 volt Class IE motor control centers IEMXI, IEMXB,2EMXI and 2EMXB.
The 600VAC Essential Auxiliary Power System is divided into two redundant and independent safety trains, each of which consists of two load centers and their associated motor control centers. Each load center normally receives power from its associated 4160 volt essential switchgear via a separate 1500KVA, 4160/600 volt essential load center transformer. The two load centers in each safety train are provided with a spare transformer which can be manually connected to either load center should the normal load center transformer be unavailable. A key interlock scheme is provided to prevent the spare transformer frorn being connected to both load centers simultaneously.
g.24 (30 NOV 1995)
o -
-: ~
TT Ac-es tot Catawba Nuclear Station 8.3 Onsite Power Systems in the event of a blackout or blackout coupled with a LOCA, the diesel generator load sequencer automatically sheds the load centers by tripping the load center incoming breakers. Essential loads required during the bid.out or blackout /LOCA condition are then automatically sequenced onto their respective bus by tb see,uencer. __
Prot ion dei s on the 600VA .ssential 'ary Power System sele and set to achieve a selecth ripp' g scheme so that a al ount of equipment is isolat m the system for adverse conditio 5 h as a fault. The load r breakers are set to protect ble feeding the essential motor con centers and coordinate w' sential motor control center eder reakers. The relays on the essen al center transformer f ders set to protect the tr ormers coordinate with the load ce er bre s.
The protective relay settings for essential systems! equipment are calculated based on equipment
/ manufacturers data and system parameters. The initial setpoints are verified during system W pre operational testing. The setpoints are determined as follows:
{ ANSI Number and Function Se_tting
- 1) load Center Incoming Breakers Set to protect the cable and equipment
%t and coordinate with feeder breaker settings.
( 2) load Center Feeder Breakers Set to protect the cable and equipment.
To avoid protective relay trip setpoint drift problems, all Class lE relays are tested periodically to verify the relays are within specified limits and are re-calibrated if required.
Refer to Section 8.3.1.4, " Independence of Redundant Systems" on page S 38 for a description of the separation of redundant equipment in the 600VAC Essential Auxiliary Power System and to Section 8.3.1.3, " Physical Identification of Class IE Equipment" on page 8-38 for a detailed description of the physical identification of safety-related equipment.
The instrumentation and control power for each redundant train of the 600VAC Essential Auxiliary Power System is supplied from the corresponding train of the 125VDC Vital Instrumentation and Control Power System as shown in Table 8-7. For a further discussion of the 125VDC vital system, refer to Section 8.3.2.1.2.1, "125VDC and 120VAC Vital Instrumentation and Control Power System" on page S-44.
B.3.1.1.2.3 Testing 8.3.1.1.2.3.1 Preoperational Testing Preoperational testing of the Class IE ac system is performed in accordance with the recommendations of Regulatory Guide 1.41 to verify proper design, installation, and operation. The preoperation test program for the emergency diesel generators is described in Section 8.3.1.1.3.10, " Prototype Qualification Program" on page S-33.
8.3.1.1.2.3.2 Periodic Testing Inspection, maintenance, and testing of the Class IE ac systems are performed on a periodic testing program in accordance with the recommendations of Regulatory Guides 1.22 and 1.118. The periodic testing program is scheduled so as not to interfere with unit operation. Where tests do not interfere with unit operation, system and equipment tests may be scheduled with the nuclear unit in operation.
(30 NOV 1995) 8-25
. -. . . . -. - - . . ~ . . . - - - . .-- _. -_- . - - - - _ . . _
W t
i T'T A <.M m1radT e L i 4
? h) SER T '
1
- Revise. the indicated portions of UFSAR section 8.3.1.1.2.2 as follows
"In general, protective devices , on the 600 ~ VAC Essential l Auxiliary Power System (EPE) are selected and set so that a j minimal-amount of equipment is isolated from the system for adverse conditions such as a fault. Protective devices ;
protect cable.and equipment. In the case of essential motor >
control center equipment, incoming breakers may not fully coordinate with motor control center load breakers. I However, the resulting amount of equipment isolation is :
acceptable, such that there is no impact on the UFSAR f Chapter 15 safety analyses and redundant equipment is not :
affected. The load center breakers are set to protect the cable feeding the essential motor control centers and ,
coordinate with the breakers that feed motor control center loads. The relays on the essential load center transformer feeders are set.to protect the transformers and coordinate with the load center breakers."
1 I
- - +e,
n Table 8-8 (Page 5 ef 5). Single Failure Analysis of the Onsite Power Systenes 5 s
Cosuponent Malfunction Safety Significance /Cosnments -
T
- 12. 600 Voh Essential Load Fault on one breaker No safety significance:
Center Source Breaker
[
M-Same as 10 above. g
- 13. 600 Voh Essential Load Bus fault No safety significance: y He 600 volt essential load center source breaker trips. The 3 loads supplied by the affected load center are lost, but the rufundant loads of the other train remain available. p;
- 14. 600 Volt Essential load Breaker fault No safety significance:
Center Feeder Breaker
.Same as 13 above. p
- 15. 600 Volt Essential load Cable fault No safety significance: h He 600 volt essential load center-feeder breaker trips. The 3 loads supplied by the affected motor control center are lost, #g but the redundant loads of the other train remain available. .-i
- 16. 600 Volt Essential Motor Bus fault No safety significance:
Contml Center Bus
, .Same as 15 above.
' 17. 600 Volt Essential Motor Cable fault No safety significance: >
j Control Center Feeder C .E m- . n . .
. __._ ll CC Cable p,1 .'2":;'M, T:l"1";M, w"";;".; a .~. . . ..n. .
,. .. . - . , ,e..
w _
Inter ock Armor &le. heaNn gnlQe 0 i
however some. kl+s heyend 4he.motorcon+
trip 4Ae mdur-Nt cen%I cenke ineom'm3 cente b
=
f 3 ) suphed b 1he. aHeded molar con %lcenler- a 3
( .are lost, hat +he. rvknitnf loads & the.
R
=
(o%er +ndn reman <ailable-. _ _ _
e a
_ ___e _
,e v
~. .
i t
Talde 8-10 (Page I of 3). Single Faelure Analysis of the 125VDC Vital Instrumentation and Controi Power Systeni E
- t Ceniponent Malfunction Safety Significance /Conunents -
T
- 1. Battery Charger loss of 600 volt ac power . No safety significance - Associated 125 volt battery is available [
supply to one battery to supply power to the 125 volt de distribution center without R-interruption. An annunciator in the' control room alerts the 4 charger operator to the malfunction.
No safety significance - Associated 125 volt battery is available ff Imss of charge'r output i to supply power to the 125 volt de distribution center without * ;
interruption. An annunciator in the control room alerts the operator to the malfunction. Additionally, a spare battery
~
charger is readily available to replace the non-functional l' charger. , ___ __
p p ,
Intemal battery charger No safety significanc .
' ^ ^
"---T----l_:#2:c-y fault r-7 f. ..y 2:,ch ,.. 5 e g y .m. ht.mi 3
{ r._ p =6- -
erS- @
u M am, y=- '!- ,n.. *' n _. ^. af a b :R. A. E_ i -- .' a
,t- -
r-..i.
- i eL hee ,'...*n-. .W - =
,k ,,
~a*m-i"-1.^_.. .e - ,Mn annu'nciator in the control --
room alerfs the operator to the malfunction. Additionally, a
- spare batte:y charger is readily available to replace the faulted charger. >
- 2. 125 solt Battery Battery fault No safety significance - Power is lost to the instrumentation and control channel served by the faulted battery; however, ;r the redundant channels continue to operate unaffected. An on annunciator in the ctmtrol room alerts the operator to the n malfunction. He faulted battery is isolated from its dc
- distribution center by the distribution center circuit breaker.
Power is restored to the affected distribution center by ,,
manually connecting it to its train associated distribution 4 center. -
g_- - - -
g
('If Ac. bdery chge.c ou.+p.& breaker- does
.I nsut not clear Ae klF Ae beery breaker my ,
3 -h4p 4.lso. Power is lost To ne. Msfr weiddion
= svtd control eknned served b9 %e. kned l
(charcodinue 3er; hheiaever, operde ne redandant unafAded. _ channe.Is.
w
- n_